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INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
Hugh K. Clark
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 351-378
Technical Paper | doi.org/10.13182/NSE82-A20279
Articles are hosted by Taylor and Francis Online.
As a contribution to a required review of the American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors, limits for homogeneous 235U systems have been recalculated to confirm their subcriticality or, where there were doubts, to propose more restrictive values. In addition, other limits were calculated to propose for inclusion in the Standard, namely limits for solutions of 235UO2(NO3)2 and limits for solutions of both UO2F2 and UO2NO3)2 that allow credit for the presence of 238U. Limits were also calculated for uranium oxides. The same three methods of calculation were used as in similar work done recently for plutonium systems. The validity of each was established by extensive correlations with pertinent critical experiments.